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Refinado por: assunto: Physics remover Nome da Publicação: Nuclear Fusion remover
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1
Power handling limit of liquid lithium divertor targets
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Power handling limit of liquid lithium divertor targets

Rindt, P. ; Morgan, T.W. ; Jaworski, M.A. ; Lopes Cardozo, N.J.

Nuclear fusion, 2018-10, Vol.58 (10), p.104002 [Periódico revisado por pares]

IOP Publishing

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2
Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI
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Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI

Rindt, P. ; Morgan, T.W. ; van Eden, G.G. ; Jaworski, M.A. ; Lopes Cardozo, N.J.

Nuclear fusion, 2019-05, Vol.59 (5), p.56003 [Periódico revisado por pares]

IOP Publishing

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3
Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses
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Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses

Rindt, P. ; Mata González, J. ; Hoogerhuis, P. ; van den Bosch, P. ; van Maris, M. ; Terentyev, D. ; Yin, C. ; Wirtz, M. ; Lopes Cardozo, N.J. ; van Dommelen, J.A.W. ; Morgan, T.W.

Nuclear fusion, 2019-05, Vol.59 (5), p.54001 [Periódico revisado por pares]

IOP Publishing

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4
Evaluating neoclassical tearing mode detection with ECE for control on ITER
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Evaluating neoclassical tearing mode detection with ECE for control on ITER

van den Brand, H. ; de Baar, M.R. ; Lopes Cardozo, N.J. ; Westerhof, E.

Nuclear fusion, 2013-01, Vol.53 (1), p.13005-13 [Periódico revisado por pares]

IOP Publishing and International Atomic Energy Agency

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5
Tearing mode stabilization by electron cyclotron resonance heating demonstrated in the TEXTOR tokamak and the implication for ITER
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Tearing mode stabilization by electron cyclotron resonance heating demonstrated in the TEXTOR tokamak and the implication for ITER

Westerhof, E ; Lazaros, A ; Farshi, E ; de Baar, M.R ; de Bock, M.F.M ; Classen, I.G.J ; Jaspers, R.J.E ; Hogeweij, G.M.D ; Koslowski, H.R ; Krämer-Flecken, A ; Liang, Y ; Lopes Cardozo, N.J ; Zimmermann, O

Nuclear fusion, 2007-02, Vol.47 (2), p.85-90 [Periódico revisado por pares]

Bristol: IOP Publishing

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6
The breakup of methane under ITER divertor hydrogen plasma conditions for carbon chemical erosion analysis with CH spectroscopy
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The breakup of methane under ITER divertor hydrogen plasma conditions for carbon chemical erosion analysis with CH spectroscopy

Westerhout, J ; Borodin, D ; Brezinsek, S ; Lopes Cardozo, N.J ; Rapp, J ; Schram, D.C ; van Rooij, G.J

Nuclear fusion, 2010-09, Vol.50 (9), p.095003 [Periódico revisado por pares]

Bristol: IOP Publishing

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7
Performance of liquid-lithium-filled 3D-printed tungsten divertor targets under deuterium loading with ELM-like pulses in Magnum-PSI
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Performance of liquid-lithium-filled 3D-printed tungsten divertor targets under deuterium loading with ELM-like pulses in Magnum-PSI

Rindt, P. ; Korving, S.Q. ; Morgan, T.W. ; Lopes Cardozo, N.J.

Nuclear fusion, 2021-06, Vol.61 (6), p.66026 [Periódico revisado por pares]

IOP Publishing

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8
Plant efficiency: a sensitivity analysis of the capacity factor for fusion power plants with high recirculated power
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Plant efficiency: a sensitivity analysis of the capacity factor for fusion power plants with high recirculated power

Mulder, R.A. ; Melese, Y.G. ; Lopes Cardozo, N.J.

Nuclear fusion, 2021-04, Vol.61 (4), p.46032 [Periódico revisado por pares]

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9
Large amplitude quasi-stationary MHD modes in JET
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Large amplitude quasi-stationary MHD modes in JET

Snipes, J.A ; Campbell, D.J ; Haynes, P.S ; Hender, T.C ; Hugon, M ; Lomas, P.J ; Lopes Cardozo, N.J ; Nave, M.F.F ; Schüller, F.C

Nuclear fusion, 1988-06, Vol.28 (6), p.1085-1097 [Periódico revisado por pares]

Bristol: IOP Publishing

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10
Application of the RTP transport model to the JET tokamak
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Application of the RTP transport model to the JET tokamak

Schilham, A.M.R ; Hogeweij, G.M.D ; Cardozo, N.J. Lopes ; Parail, V.V ; Gormezano, C

Nuclear fusion, 2002-05, Vol.42 (5), p.581-590, Article 581 [Periódico revisado por pares]

Bristol: IOP Publishing

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